In this study, the D-3He fusion reaction was investigated by magnetic confinement in the ITER-90HP Tokamak reactor. D-3He, among other nuclear fuels, because of higher efficiency, direct conversion of energy and reduction of radiation hazards and lower maintenance costs is attractive. With this aim, time variations of temperature, gain and density in two cases, without purity and in the presence of purities of argon and beryllium, were obtained by solving energy balance equations, and using the fuel injection control method, taking into account a 20% disruption at the initial temperature improved inherent instabilities.